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Journal ArticleDOI

Delayed hydride cracking in Zr–2.5Nb pressure tube material☆

01 Aug 2002-Journal of Nuclear Materials (North-Holland)-Vol. 304, Iss: 2, pp 189-203
TL;DR: In this paper, the authors measured the DHC velocity along the axial direction of the double melted, cold worked and stress-relieved Zirconium-2.5Niobium pressure tube material in the temperature range of 162-283 °C.
About: This article is published in Journal of Nuclear Materials.The article was published on 2002-08-01. It has received 58 citations till now.
Citations
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Journal ArticleDOI
TL;DR: In this paper, the authors provide a concise summary of experimental and computational studies performed on hydride precipitation in zirconium alloys since the 1960's, with specific consideration given to the phase field model, which has become a popular and powerful computational tool for modeling microstructure evolution.

106 citations

Journal ArticleDOI
TL;DR: In this paper, the effect of reoriented hydrides on the tensile properties of the Zr-2.5 wt% Nb pressure tube alloy was evaluated in the temperature range of 298-573 K.

98 citations

Journal ArticleDOI
TL;DR: In this article, the terminal solid solubility (TSS) of hydrogen for Zr-alloy pressure tube materials was determined corresponding to end of hydride dissolution (TSSD) and start of hydrogen precipitation (TSSP) using the dilatometry technique.

74 citations

Journal ArticleDOI
TL;DR: In this paper, the composition and microstructure of the oxide layers were characterized by X-ray photoelectron spectroscopy (XPS), XRD, scanning electron microscopy with energy dispersive spectroscope (SEM/EDS), and potentiodynamic polarization measurements were used to assess the mechanical and electrochemical properties of the PEO coatings.

45 citations

Journal ArticleDOI
TL;DR: In this paper, the terminal solid solubilities of hydrides dissolution (TSSD) during heatup and precipitation (TSSP) during cooldown for N18, Zry-4 and M5 alloys with hydrogen concentrations of 20-240ppm were measured by differential scanning calorimetry (DSC) in the range of 50-500°C.

35 citations

References
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Journal ArticleDOI
TL;DR: In this paper, a model that is capable of accounting for the hysteresis observed in the measured terminal solid solubilities (TSS) of metal hydride systems is presented.

129 citations

Journal ArticleDOI
TL;DR: In this article, the terminal solid solubility (TSS) of Zr alloys that are used in the nuclear industry is modeled as a function of temperature and the hysteresis between hydride dissolution and precipitation is studied.

126 citations

Journal ArticleDOI
TL;DR: The general field of environmentally-induced cracking of zirconium alloys has been reviewed and the phenomena that are observed and the progress in understanding the mechanisms are summarized in this article.

117 citations

Journal ArticleDOI
TL;DR: In this paper, a modified route involving hot extrusion followed by two pilgering operations with an intermediate annealing step was examined in detail, with the main aim of this work being to produce a microstructure and texture which are known to yield a lower irradiation growth.
Abstract: Microstructural changes occurring during the fabrication of Zr-2.5 pct Nb alloy pressure tubes by a modified route, involving hot extrusion followed by two pilgering operations with an intermediate annealing step, have been examined in detail. In the conventional fabrication route, the hot extrusion step is followed by a single cold drawing operation in which the cold work to the extent of 25 pct is imparted to the material for achieving the required mechanical properties. Tensile properties obtained at each stage of fabrication have been evaluated and compared between the two processes. The main aim of this work has been to produce a microstructure and texture which are known to yield a lower irradiation growth. Additionally, suitable annealing conditions have been optimized for the intermediate annealing which annihilates the cold work introduced by the first cold pilgering operation without disturbing the two-phase elongated microstructure. This elongated α+ β I microstructure is required for obtaining the desired level of strength at 310 °C. The final microstructure and the crystallographic texture of the finished pressure tube have been compared with those reported for the conventionally processed material.

103 citations

Journal ArticleDOI
TL;DR: In this article, cold-worked Zr-2.5 wt% Nb pressure tubes for Canada Deuterium Uranium Pressurized Heavy Water Reactors are made by hot extruding hollow billets into tubes that are cold worked to size and to develop their tensile strength.
Abstract: Cold-worked Zr-2.5 wt% Nb pressure tubes for Canada Deuterium Uranium Pressurized Heavy Water Reactors are made by hot extruding hollow billets into tubes that are cold-worked to size and to develop their tensile strength. All manufacturing steps are closely controlled, and the tubes meet very stringent specifications. To ensure that the tubes are free of unacceptable defects, the ingots, billets, and finished tubes are ultrasonically inspected. The strength and flaw tolerance of the tubes have been measured. Tubes removed from both research and operating power reactors have been examined to measure changes in each of these properties due to the effects of reactor operaton. All tests show that cold-worked Zr-2.5 wt% Nb pressure tubes have excellent tensile strength and resistance to failure.

72 citations